Survey on vertical two-phase countercurrent flooding. [BWR; PWR]
One important problem in the safety analysis of a light water reactor is the flooding phenomenon or the countercurrent flow limit in the reflood process of the reactor core during a hypothetical loss-of-coolant accident. Published analytical models for predicting this limiting condition based on the analysis of hanging films and on the theory of small distrubance in falling films are reviewed. Existing experimental results and empirical correlations are summarized, and the parametric dependence of the countercurrent flow limit is discussed. Also included in the survey are various extended problems in flooding including those with vapor condensation, liquid entrainment, flow inclination, complex system geometries and multiple channels.
- Research Organization:
- California Univ., Berkeley (USA). Dept. of Mechanical Engineering
- OSTI ID:
- 6494135
- Report Number(s):
- EPRI-NP-984
- Country of Publication:
- United States
- Language:
- English
Similar Records
Flooding in two-phase countercurrent flows. [PWR; BWR]
Review of entrainment phenomena and application to vertical two-phase countercurrent flooding. [PWR; BWR]
Vertical slip flow and flooding models in LOCA analysis
Technical Report
·
Fri Nov 30 23:00:00 EST 1979
·
OSTI ID:5399817
Review of entrainment phenomena and application to vertical two-phase countercurrent flooding. [PWR; BWR]
Technical Report
·
Fri Nov 30 23:00:00 EST 1979
·
OSTI ID:5378707
Vertical slip flow and flooding models in LOCA analysis
Conference
·
Sun Jun 01 00:00:00 EDT 1975
·
OSTI ID:4120578
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS